Demand driven salt clean-up in a molten salt fast reactor – Defining a priority list

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Abstract

The PUREX technology based on aqueous processes is currently the leading reprocessing technology in nuclear energy systems. It seems to be the most developed and established process for light water reactor fuel and the use of solid fuel. However, demand driven development of the nuclear system opens the way to liquid fuelled reactors, and disruptive technology development through the application of an integrated fuel cycle with a direct link to reactor operation. The possibilities of this new concept for innovative reprocessing technology development are analysed, the boundary conditions are discussed, and the economic as well as the neutron physical optimization parameters of the process are elucidated. Reactor physical knowledge of the influence of different elements on the neutron economy of the reactor is required. Using an innovative study approach, an element priority list for the salt clean-up is developed, which indicates that separation of Neodymium and Caesium is desirable, as they contribute almost 50% to the loss of criticality. Separating Zirconium and Samarium in addition from the fuel salt would remove nearly 80% of the loss of criticality due to fission products. The theoretical study is followed by a qualitative discussion of the different, demand driven optimization strategies which could satisfy the conflicting interests of sustainable reactor operation, efficient chemical processing for the salt clean-up, and the related economic as well as chemical engineering consequences. A new, innovative approach of balancing the throughput through salt processing based on a low number of separation process steps is developed. Next steps for the development of an economically viable salt clean-up process are identified.

Figures

  • Fig 1. Geometry of the model reactor used in this study.
  • Table 1. Plutonium vector used in calculations.
  • Table 2. Summary of the variants used in the sensitivity study.
  • Fig 2. Elementary composition of the used spent nuclear fuel composition as calculated by FISPIN.
  • Fig 3. Fission products elements which are dissolved in the salt and are observed for the salt clean-up based on the list given in the EVOL benchmark.
  • Fig 4. Sensitivity list for the observed chemical elements based on the EVOL benchmark element list using the extraction method for the simulation.
  • Fig 5. Sensitivity list for the observed chemical elements based on the EVOL benchmark element list using the addition approach for the simulation.
  • Fig 6. Cross check of the influence of the molar fraction cut-off on the sensitivity list.

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CITATION STYLE

APA

Merk, B., Litskevich, D., Gregg, R., & Mount, A. R. (2018). Demand driven salt clean-up in a molten salt fast reactor – Defining a priority list. PLoS ONE, 13(3). https://doi.org/10.1371/journal.pone.0192020

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